standard deviation

Assessment of Design Approximation Impact on Neutronic Characteristics of a High-Temperature Gas-Cooled Reactor Fuel Assembly

3/18/2024 2024 - #01 Modelling processes at nuclear facilities

Salyaev A.V. Usynina S.G. Kalinina V.P.

Brittle fracture resistance of reactor pressure vessel steels in the initial state

3/23/2018 2018 - #01 Nuclear materials

Anosov N.P. Skorobogatykh V.N. Gordyuk L.Yu. Mikheev V.A. Pogorelov E.V. Shamardin V.K.